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《Powder Metallurgy Technology》 2017-01
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Study on pressless sintering of B_4C pellets used in nuclear reactors

LI Yuan-yuan;LIU Hai;LI Tong-ye;YANG Jing;PANG Xiao-qiang;ZHANG Yu;Nuclear Power Institute of China;State Key Laboratory for Nuclear Fuel and Materials;  
By using the high pure B_4C powder as the starting material and the phenol-formaldehyde resin as the sintering aids and binders,the B_4C pellets were prepared by die pressing and then held at 2250 ℃ for 40 min.The chemical components of raw powder and pellets were analyzed by chemical analytical methods,the densities of pellets were characterized by Archimedes method,the microstructures of pellets were observed by scanning electron microscopy(SEM),and the deformation of the B_4C annual pellets were investigated and summarized.The results show that carbon has the remarkable effect on the densification of B_4C pellets,the density of B_4C pellets increases significantly with increasing carbon content,the maximum value of 2.35 g/cm~3 is obtained at the carbon content of 5wt%,and B_4C pellets with the sintered density of 2.0 g/cm~3 is obtained by adding 3wt% carbon.The chemical content and other technical indexes can meet the requirement of the B_4C pellets used in nuclear reactors.
【CateGory Index】: TL352.21
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